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management and ALARA requirements applicable to the design activities of the Spent Nuclear Fuel. Project, and establishes consistency of information used by multiple subprojects in ALARA evaluations. method for meeting the ALARA requirements applicable to facility designs involves two components. The first is each Spent Nuclear Fuel Project subproject incorporating ALARA principles, ALARA design optimizations, and ALARA design reviews throughout the design of facilities and equipment. The second component is the Spent Nuclear Fuel Project management providing overall dose management guidance to the subprojects and oversight of the subproject dose management efforts.

This document describes the operational t e s t i n g a t t h e KE Basin planned f o r demonstrating and evaluating a high f l u x back washable f i l t e r. t e s t i n g t o be conducted, the samples and measurements t o be taken, the sample analysis t o be performed, and the use o f the information obtained. The document includes the d e s c r i p t i o n o f the operational TRADEMARK DISCLAIMER. Reference herein t o any specific c m r c i a l product, process, or service by trade name, trademsrk, manufacturer, or otherwise, does not necessariiy constitute or imply i t s endorsement, r e c m n d a t i o n , or favoring by the United States Cavermnt OP any agency thereof or i t s contractors or subcontractors.

SUMMARYThe subject analysis has been reviewed to determine if calculations are valid within stated assumptions. and suggest ways of reducing conservatism. Hand-calculations show that calculations have been performed correctly within the stated assumptions, although sludge density and uranium content have been used inconsistently in the text. VALIDATIONHand-calculations demonstrate that the subject results are reasonable, given the stated assumptions.A simple model suitable for hand-calculation assumes the following: (1) the t e m p e r a h drop across the first and second layers is zero, (2) volumetric beat generation is significant only in the third layer. (3) heat conduction is one-dimensional. and. (4) the bottom surface of the sludge is adiabatic while the top is fixed at IO C, and, (5) heat generation due to oxidation in the third layer can be r e p r m t e d by using one equivalent temperature in the oxidation rate law.A solution then for the temperature rise across the third layer is then:where Q"' is the volumetric heat generation due to decay heat and oxidation, L is the thickness of the third layer, and k is the sludge t h d conductivity. Figure 1 of the s u b w analysis gives L = 49 cm, and k = 0.6 Wk-m. Volumetric beat generation rate due to decay heat (m W/m ) is given by:where rsl is the third layer sludge density, Q is the heat generation rate in tefms of kWkg U, and U is the uranium concentration. Volumetric heat generation due to oxidation (W/m ) is given by:Q"', = 1000 rslmu (0.0068) 10(7.364 3016/r) where RM is rate multiplier, and T is an effective temperature. The effective temperature should yield the total volumetric heat generation rate in the third sludge layer. Appropriate v a l u~ for the analysis base case are: Q = 0.073 KW/ h4T U, RM = 0.82, U = 0.76 kg U/ kg SI, and rsl = 2300 kg/m . From Figure 1 of the subject analysis, the temperature of sludge varies between 283 and 325 K. which suggests that T might be somewhere in the range of 3 IO to 320 K. The effective temperature T was varied parametrically, as shown in Table 1 : 0.49The actual temperature rise across the third layer sludge is about 42 K, which is in fair agreement with results shown in Table 1.Total volumetric heat generation for the subject analysis was found from the temperature distribution shown in Table I, a total volumetric heat generation rate of 189 W/m3 gives a temperature rise of about 38 K, which agrees reasonably well with the 42 K value calculated for the subject analysis, and demonstrates that the temperature distribution in Figure 1 of the subject analysis is correct within stated assumptions. Disagreement between the hand-calculation and the subject analysis can be attributed to neglect of the fmt and second layers in the hand-calculation. COMMENTS AND SUGGESTIONSThe text on page A-10 is inconsistent. Decay heat is listed as 0.073 kW/MT U and from the SNF Project Technical Databook, WHC-SD-SNF-TI-015, this appears to be correct. But the uranium content of wet sludge should be used in calculations by cons...

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